#include <FissionRateAux.h>
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| const MaterialProperty< std::vector< Real > > & | _fissxs |
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| unsigned int | _num_groups |
| | Number of neutron groups.
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| Real | _nt_scale |
| | Neutron flux scaling factor.
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| std::vector< const VariableValue * > | _group_fluxes |
| | Group flux variables.
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Computes heat source due to fission during a transient. This is the same as FissionHeatSourceAux, but with the exception that the power is not normalized to some user-defined value. The reactor will produce heat freely. You'll probably see thermal feedback since MSRs are nice like that.
◆ FissionRateAux()
| FissionRateAux::FissionRateAux |
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const InputParameters & | parameters | ) |
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◆ computeValue()
| Real FissionRateAux::computeValue |
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overrideprotectedvirtual |
◆ validParams()
| InputParameters FissionRateAux::validParams |
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static |
◆ _fissxs
| const MaterialProperty<std::vector<Real> >& FissionRateAux::_fissxs |
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protected |
◆ _group_fluxes
| std::vector<const VariableValue *> FissionRateAux::_group_fluxes |
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◆ _nt_scale
| Real FissionRateAux::_nt_scale |
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Neutron flux scaling factor.
◆ _num_groups
| unsigned int FissionRateAux::_num_groups |
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Number of neutron groups.
The documentation for this class was generated from the following files: